Characterization of in-situ and ex-situ ion-irradiated additively manufactured 316L and 316H stainless steels

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-08-06 DOI:10.1016/j.jnucmat.2025.156044

Wei-Ying Chen , Stephen Taller , Andrea M. Jokisaari , Yiren Chen , Rongjie Song , Xuan Zhang , Lin Gao , Peter M. Baldo , Dzmitry Habaruk , Meimei Li

{"title":"Characterization of in-situ and ex-situ ion-irradiated additively manufactured 316L and 316H stainless steels","authors":"Wei-Ying Chen , Stephen Taller , Andrea M. Jokisaari , Yiren Chen , Rongjie Song , Xuan Zhang , Lin Gao , Peter M. Baldo , Dzmitry Habaruk , Meimei Li","doi":"10.1016/j.jnucmat.2025.156044","DOIUrl":null,"url":null,"abstract":"<div><div>Additively manufactured (AM) 316 stainless steel (SS) differs from its wrought counterpart in its unique dislocation cell structure and the presence of segregation and oxide particles at the cell walls. This work investigated the evolution of the microstructure in laser powder bed fusion (LPBF) 316L and 316H SS under <em>in-situ</em> 1 MeV Kr ion irradiation at 600°C to 5 dpa, and <em>ex-situ</em> 4 MeV Ni ion irradiation at 300°C and 600°C from 0.2 dpa to 10 dpa, with a dose rate for all experiments of 10<sup>-3</sup> dpa/s. The results reveal that the dislocation cell structure results in heterogeneous formation of dislocation loops and voids, particularly at 600°C, where loops tend to form within the cell interiors while voids form at the cell boundaries. LPBF 316H has a reduced level of swelling compared to LPBF 316L due to prolonged incubation. Energy Dispersive X-ray Spectroscopy (EDS) mapping indicates Ni and Si segregation at void surfaces due to radiation-induced segregation. At 300°C, where voids are absent, the distribution of dislocation loops and stacking fault tetrahedra appears to be uniform. Dislocation cell structures mostly disappeared by 2 dpa for all conditions in this work. M<sub>23</sub>C<sub>6</sub> carbides were observed in LPBF 316H at 600°C as early as 0.2 dpa, but not in LPBF 316L. Nanoindentation was performed to obtain the hardness of irradiated materials. This work illustrated the influence of additive manufacturing processes on microstructure evolution under irradiation, revealing the differences as well as the similarities as compared with wrought 316 SS, and the AM-related phenomenon that can potentially occur under neutron irradiation in nuclear reactors.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"616 ","pages":"Article 156044"},"PeriodicalIF":3.2000,"publicationDate":"2025-08-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525004386","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}

引用次数: 0

Abstract

Additively manufactured (AM) 316 stainless steel (SS) differs from its wrought counterpart in its unique dislocation cell structure and the presence of segregation and oxide particles at the cell walls. This work investigated the evolution of the microstructure in laser powder bed fusion (LPBF) 316L and 316H SS under in-situ 1 MeV Kr ion irradiation at 600 °C to 5 dpa, and ex-situ 4 MeV Ni ion irradiation at 300 °C and 600 °C from 0.2 dpa to 10 dpa, with a dose rate for all experiments of 10^-3 dpa/s. The results reveal that the dislocation cell structure results in heterogeneous formation of dislocation loops and voids, particularly at 600 °C, where loops tend to form within the cell interiors while voids form at the cell boundaries. LPBF 316H has a reduced level of swelling compared to LPBF 316L due to prolonged incubation. Energy Dispersive X-ray Spectroscopy (EDS) mapping indicates Ni and Si segregation at void surfaces due to radiation-induced segregation. At 300 °C, where voids are absent, the distribution of dislocation loops and stacking fault tetrahedra appears to be uniform. Dislocation cell structures mostly disappeared by 2 dpa for all conditions in this work. M₂₃C₆ carbides were observed in LPBF 316H at 600 °C as early as 0.2 dpa, but not in LPBF 316L. Nanoindentation was performed to obtain the hardness of irradiated materials. This work illustrated the influence of additive manufacturing processes on microstructure evolution under irradiation, revealing the differences as well as the similarities as compared with wrought 316 SS, and the AM-related phenomenon that can potentially occur under neutron irradiation in nuclear reactors.

查看原文本刊更多论文

原位和非原位离子辐照增材制造316L和316H不锈钢的表征

增材制造（AM） 316不锈钢（SS）的不同之处在于其独特的位错细胞结构和细胞壁上的偏析和氧化物颗粒的存在。研究了激光粉末床熔合（LPBF） 316L和316H SS在600°C至5 dpa的原位1mev氪离子照射和300°C和600°C 0.2至10 dpa的非原位4mev Ni离子照射下的微观结构演变，实验剂量率均为10-3 dpa/s。结果表明，位错细胞结构导致位错环和空隙的不均匀形成，特别是在600°C时，环路倾向于在细胞内部形成，而空隙则在细胞边界形成。与LPBF 316L相比，LPBF 316H由于孵育时间较长，肿胀程度较低。能量色散x射线能谱（EDS）作图表明，Ni和Si在空洞表面的偏析是由辐射引起的。在300℃时，无空洞，位错环和层错四面体分布均匀。在所有条件下，位错细胞结构在2 dpa时基本消失。在600℃时，早在0.2 dpa时，LPBF 316H中就观察到M23C6碳化物，而LPBF 316L中没有。采用纳米压痕法测定辐照材料的硬度。这项工作说明了增材制造工艺对辐照下微观结构演变的影响，揭示了与变形316 SS相比的差异和相似之处，以及核反应堆中子辐照下可能发生的am相关现象。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.